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MONTHYEARML0325911522003-09-0505 September 2003 Technical Specifications Change 425 - Framatome Fuel - Core Operating Limits Report References - Response to Request for Additional Information and TS Mark-up Correction Project stage: Response to RAI ML0331601782003-11-0707 November 2003 Technical Specifications (TS) Change 425 - Framatome Fuel - Core Operating Limits Report (COLR) Reference - Response to Request for Additional Information (RAI) Project stage: Response to RAI ML0336501422003-12-30030 December 2003 License Amendments, Revising Technical Specifications 3.3.4.1, 3.7.5, & 5.6.5 to Add References to Framatome Advanced Nuclear Power Analytical Methods That Will Be Used to Determine Core Operating Limits Project stage: Other ML0400203052003-12-30030 December 2003 Tech Spec Pages for Amendment No. 287, Revising Technical Specifications 3.3.4.1, 3.7.5, & 5.6.5 to Add References to Framatome Advanced Nuclear Power Analytical Methods That Will Be Used to Determine Core Operating Limits Project stage: Other ML0400203152003-12-30030 December 2003 Tech Spec Pages for Amendment No. 245, Revising Technical Specifications 3.3.4.1, 3.7.5, & 5.6.5 to Add References to Framatome Advanced Nuclear Power Analytical Methods That Will Be Used to Determine Core Operating Limits Project stage: Other 2003-12-30
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Category:Letter
MONTHYEARIR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24106A2432024-04-16016 April 2024 Letter to Federally Recognized Tribes-Ben, Mississippi Band of Choctaw Indians ML24106A2512024-04-16016 April 2024 Letter to Federally Recognized Tribes-Morrow, Thlopthlocco Tribal Town ML24106A2632024-04-16016 April 2024 Ltr to State Recognized Tribes-Hamilton, Cher-O-Creek Intra Tribal Indians ML24106A2462024-04-16016 April 2024 Letter to Federally Recognized Tribes-Cypress, Miccosukee Tribe ML24107A0032024-04-16016 April 2024 Letter to Federally Recognized Tribes-Pierite, Tunica-Biloxi Tribe of Louisiana ML24106A2592024-04-16016 April 2024 Ltr to State Recognized Tribes-Bridges, United Cherokee Aniynwiya ML24106A2452024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Cernek, Couchatta Tribe of Louisiana ML24106A2622024-04-16016 April 2024 Ltr to State Recognized Tribes-Gilmore, Southeastern Mvskoke Nation ML24106A2472024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Hicks, Eastern Band of Cherokee Indians ML24106A2542024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Rogers, Jena Band of Choctaw Indians ML24106A2652024-04-16016 April 2024 Letter to State Recognized Tribes-Wright, Ma-Chis Lower Creek Indian Tribe of Alabama ML24102A0422024-04-16016 April 2024 Ltr to State Recognized Tribes-Russell, Cherokee Tribe of Northeast Alabama ML24106A2482024-04-16016 April 2024 Letter to Federally Recognized Tribes-Hill, Muscogee (Creek) Nation ML24102A0412024-04-16016 April 2024 Ltr to SHPO-Request for Scoping Comments Concerning the Env Review of the Browns Ferry Subsequent License Renew App ML24106A2382024-04-16016 April 2024 Letter to Federally Recognized Tribes-Anoatubby, Chickasaw Nation ML24106A2572024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Yahola, Kialegee Tribal Town ML24106A2562024-04-16016 April 2024 Letter to Federally Recognized Tribes-Wallace, Eastern Shawnee Tribe of Oklahoma ML24107A0022024-04-16016 April 2024 Letter to Federally Recognized Tribes-Bunch, United Keetoowah Band of Cherokee Indians ML24106A2492024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Hoskin, Jr., Cherokee Nation ML24106A2412024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Battise, Alabama-Coushatta Tribe of Texas ML24106A2402024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Barnes, Shawnee Tribe 2024-08-06
[Table view] Category:Technical Specification
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) ML21335A0672021-11-26026 November 2021 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions ML24019A1192021-04-0808 April 2021 Technical Specification 3.1.6, Rod Pattern Control CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-062, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 12018-04-19019 April 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus ML18066A1202018-02-20020 February 2018 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions - Updated CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change2016-10-31031 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information CNL-16-073, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information2016-04-22022 April 2016 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information CNL-15-240, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information2015-11-13013 November 2015 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..2015-09-25025 September 2015 Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In.. NL-15-169, Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 32015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 3 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 42015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1692015-09-21021 September 2015 Proposed Technical Specification Markups, Part 2 of 2 ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 52015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1802015-09-21021 September 2015 Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1782015-09-21021 September 2015 Retyped Proposed Technical Specifications Changes, Attachment 3 ML15282A1672015-09-21021 September 2015 License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes ML15282A1792015-09-21021 September 2015 Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1662015-09-21021 September 2015 Proposed Technical Specification Markups, Part 1 of 2 CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)2015-03-0606 March 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499) CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)2015-02-17017 February 2015 Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479) CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML12242A4772012-08-28028 August 2012 License Amendment Request to Change Technical Specifications to Delete References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25 Percent Extension of Surveillance Intervals to Accel ML1106004082011-02-25025 February 2011 Technical Specification Change TS-429 - Deletion of Low Pressure Coolant Injection Motor-Generator Sets ML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D ML1024305282010-08-27027 August 2010 Technical Specifications Change TS-474 - Request to Add TS 3.7.3, Control Room Emergency Ventilation (Crev) System, Action to Address Two Crev Subsystems Inoperable Due to Inoperable Crev System High Efficiency Particulate ML1005507002010-02-18018 February 2010 Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D ML0933506552009-11-17017 November 2009 Technical Specification Change TS-467-S - Utilization of Areva Fuel & Associated Analysis Methodologies - Non EPU Supplement ML0930801582009-10-23023 October 2009 Technical Specification Change TS-467 - Utilization of Areva Fuel and Associated Analysis Methodologies ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0922904712009-08-11011 August 2009 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation ML0921101192009-07-27027 July 2009 Technical Specifications Change 465 - Revision of Technical Specifications to Eliminate Unnecessary Water Local Leak Rate Tests 2023-03-10
[Table view] Category:Bases Change
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) ML21335A0672021-11-26026 November 2021 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 ML18066A1202018-02-20020 February 2018 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions - Updated CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change2016-10-31031 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates CNL-16-073, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information2016-04-22022 April 2016 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information CNL-15-240, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information2015-11-13013 November 2015 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..2015-09-25025 September 2015 Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In.. CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML1106004082011-02-25025 February 2011 Technical Specification Change TS-429 - Deletion of Low Pressure Coolant Injection Motor-Generator Sets ML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D ML1024305282010-08-27027 August 2010 Technical Specifications Change TS-474 - Request to Add TS 3.7.3, Control Room Emergency Ventilation (Crev) System, Action to Address Two Crev Subsystems Inoperable Due to Inoperable Crev System High Efficiency Particulate ML1005507002010-02-18018 February 2010 Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D ML0922904712009-08-11011 August 2009 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation ML0921101192009-07-27027 July 2009 Technical Specifications Change 465 - Revision of Technical Specifications to Eliminate Unnecessary Water Local Leak Rate Tests ML0915400152009-05-29029 May 2009 Technical Specifications Changes TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 24 Request for Additional Information (RAI) EMCB.209 Regarding Steam Dryer Analyses ML0912000642009-04-24024 April 2009 Technical Specifications Change 464 - Application for Technical Specification Improvement to Adopt Technical Specification Task Force TSTF-476, Rev. 1, Improved BPWS Control Rod Insertion Process ML0904402062009-02-0909 February 2009 Response for Additional Information Regarding - Technical Specifications (TS) Change 444 - Adoption of Changes to Standard Technical Specifications Under Technical Specification Task Force (Tstf). ML0836501092008-12-22022 December 2008 Technical Specifications Change 463-T, One-time Extension of Surveillance Requirements (Srs) ML0835306192008-12-15015 December 2008 Technical Specifications Change TS-431 - Extended Power Uprate - Response to Round 22 Request for Additional Information - Unit 1 Large Transient Testing (Ltt) - ML0829602272008-10-17017 October 2008 Technical Specifications Change TS-418 - Extended Power Uprate - Response to Round 21 Request for Additional Information on Channel Bow ML0723602632007-08-31031 August 2007 07-31NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry, Unit 2 and 3, Revision 0 ML0723602622007-08-31031 August 2007 07-30NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry, Unit 1, Revision 0 ML0721303752007-07-31031 July 2007 CDI Report No. 07-05NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 1, Steam Dryer to 250 Hz ML0721303822007-07-31031 July 2007 CDI Report No. 07-06NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 2 & 2 Steam Dryer to 250 Hz ML0721303862007-07-31031 July 2007 CDI Report No. 07-09NP, Revision 0, Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with Inclusion of a Low Frequency Hydrodynamic Contribution ML0721304152007-07-31031 July 2007 CDI Report No. 07-11NP, Revision 0, Dynamics of BWR Steam Dryer Components ML0721304292007-07-31031 July 2007 C.D.I. Technical Memorandum No. 07-26NP, Revision 0, Comparison of Browns Ferry Unit 1 & Unit 2 Main Steam Line Strain Gage / Pressure Readings ML0721304012007-07-31031 July 2007 CDI Report No. 07-10NP, Revision 0, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry, Unit 2, Steam Dryer to 250 Hz ML0710100922007-04-0606 April 2007 (BFN) - Unit 3 - Technical Specifications (TS) Change TS-460-T - Request for One-Time Extension of Allowed Outage Time (AOT) - Emergency Diesel Generator (EDG) 3D ML0706003392007-02-26026 February 2007 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) - Response to Round 12 Request for Additional Information (RAI) ML0628602672006-10-0505 October 2006 Technical Specification Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 10 Request for Additional Information ML0627902302006-10-0303 October 2006 Technical Specifications Changes TS-431 and TS 418 - Extended Power Uprate - Steam Dryer Stress Report, Revision 4 ML0627901402006-10-0202 October 2006 Technical Specifications Change TS-443 - Request for Additional Information (RAI) Regarding Oscillation Power Range Monitor ML0629201562006-09-13013 September 2006 Rev 1 to Technical Specification, NPSH Transient Study RHR and Core Spray Pumps, E12.5.1296 ML0617803082006-06-15015 June 2006 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 5 Request for Additional Information ML0625103852006-05-31031 May 2006 Enclosure 3, Browns Ferry, Units 1, 2 & 3 - CDI Report No. 05-28P, Rev 1, Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements. ML0613004432006-05-31031 May 2006 GE-NE-0000-0053-7413-R0-NP, Browns Ferry, Units 1, 2 & 3 Steam Dryer Stress, Dynamic and Fatigue Analyses for EPU Conditions. ML0613004412006-05-31031 May 2006 C.D.I. Report 06-11, Rev 1, Hydrodynamic Loads on Browns Ferry, Unit 1 Steam Dryer to 200 Hz. ML0613601482006-05-11011 May 2006 Supplemental Response to NRC Round 3 Request for Additional Information Related to Technical Specifications Change No. TS-418 - Extended Power Uprate Operation ML0613004362006-05-0505 May 2006 Transmittal of Browns Ferry, Units 1, 2 & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Steam Dryer Stress Report ML0606203282006-02-28028 February 2006 Technical Specifications (TS) Change TS-431 - Response to Request for Additional Information SPSB-A.11 Regarding Extended Power Uprate - Credit for Net Positive Suction Head 2023-03-10
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Tennessee Valley Authority, Post Office Box 2000. Decatur, 'abara 35609-2000 TVA-BFN-TS-425 10 CFR 50.90 September 5, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk-Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of) Docket Nos. 50-260 Tennessee Valley Authority 50-296 BROWNS FERRY-NUCLEAR PLANT BFN) UNITS 2 AND 3 TECHNICAL SPECIFICATIONS (TS) CHANGE-425 - FRAMAOME FUEL -CORE OPERATING LIMITS REPORT-(COLR) REFERENCES--- RESPONSE TO REQUEST FOR ADDITIONAL INFORK&TION (RAI) AND TS MARK-UP CORRECTION (TAC NOS. MB8433, MB8434)
This letter is-in response to a June 20, 2003, teleconference with the NRC staff regarding proposed BFN-TSchange 425. The proposed amendment,_which was submittedon April 14, 2003, revises two Limiting Conditions for peration regarding core thermal limits adjustments for inoperableequipment and modifies TS 5.6.5, COLR, to add references to the Frantatome Advanced Nuclear Power analytical methods that will be used to determine core operating limits.
NRC subsequently provided two-RAI questions related to the proposed TS 5.6.5 changes regardingCOLR references. The two RAI questions are repeated in Enclosure along with TVA's response.
NRrvie ubeuety woRI ustos eatdt t A correction to the TS mark-up pages provided in TVA's April 14, 2003, submittal has also been identified. The last word in the hhe new LCO 3.3.4..c should be changed from operable" to Pritnd on rEcWd
U.S. Nuclear Regulatory Commission Page 2 September 5, 2003 "applicable" for consistency with the associated TS Condition.
This is an administrative change and does not affect the purpose of the proposed TS. Replacement Unit 2 and 3 mark-up pages are provided in Enclosure 2.
TVA has determined this additional information response does not change the determination in the April 14, 2003, TS-425 submittal that there are no significant hazards considerations associated with the proposed change and that the TS change qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)-(9). Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and the Enclosure to the Alabama State Department of Public Health.
There are no regulatory commitments associated with this submittal. This letter is being sent in accordance with NRC Regulatory Issue Summary 2001-05, Guidance on Submitting Documents to the NRC by Electronic Information Exchange or on CD-ROM. If you have any questions about this submittal or TS-425, please contact me at (256) 729-2636.
I declare under penalty of perjury that the foregoing is true and correct. Executed on September 5, 2003.
St cere 5yt T. E. Abney Manager Licensing and dustry Affai s Enclosu es:
- 1. Res nse to est for Additional Information (RAI)
- 2. Correc e S Pages (mark-up)
Enclosures cc (Enclosures):
State Health Officer Alabama State Department of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017
Enclosure 1 Technical Specifications (TS) Change 425 Framatome Fuel - Core Operating Limits Report (COLR)
References Units 2 and 3 Response to Request for Additional Information NRC Question 1 Since the licensee is planning a transition to Framatome ANP fuel while still keeping some of the previous fuel in the core, the licensee will retain the existing reference to the Global Nuclear Fuels topical. In the modified version of TS 5.6.5.b, after the reference to NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel, the licensee requests the removal of the statement latest approved version for BFN." Please provide justification for removing this statement from the reference document. What-version of this document will be used for the upcoming fuel cycle, and is it the most recent?
TVA Response As discussed in the April 14, 2003, TS-425 submittal, the proposed change to TS 5.6.5.b-adopts the syntax of TS Task Force (TSTF) Traveler 363. TSTF-363 was approved by NRC on July 6, 2000, and provides that only the titles of the analytic methods be included in TS 5.6.5.b and that the complete identification (report number, title, revision, date, and any supplements) be maintained in the Core Operating Limits Report COLR).
Therefore, the removal of the existing phrase "latest approved version for BFN" after the reference to NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel", is being made to stay consistent with the TSTF. By adopting TSTF-363, BFN is updating this section of TS to the latest NRC-approved version of NUREG-1433 Revision 2, "Standard TS for BWR/4s."
The existing TS 5.6.5.b reference to the Global Nuclear Fuels (GNF) (formerly General Electric) topical report, NEDE-24011-P-A, will be retained pending the complete replacement of GNF fuel with Framatome Advance Nuclear Power (FANP) fuel, since some GNF-derived core limits will continue to be applicable for
co-resident GNF fuel. NEDE-24011-P-A-14 is the latest version approved for use by NRC for BFN.
NRC Question 2 In the TS section 5.6.5 Core Operating Limits Report part (a),
four limits and setpoints are listed which the licensee calculates for each reload cycle. The licensee requests the addition of 16 approved methodologies in 5.6.5.b which will be used to calculate these limits. The licensee has not provided any indication of which individual methodologies it plans on using to calculate each limit. Please provide the staff with a table indicating which methodology will be used to calculate each limit for each fuel assembly type during the fuel transition.
TVA Response A table is provided in Attachment A, which shows the 16 FANP references added to TS 5.6.5.b by TS-425 and the associated TS 5.6.5.a Limiting Conditions for Operation-for the core limits or setpoints for which the methodology is used. Additionally, Attachment B shows the applicability of the retained reference, GNF topical report NEDE-24011-P-A, to the TS 5.6.5.a core limits.
Details regarding GNF methods for calculating core limits are available in NEDE-24011-P-A-4, June 2000.
2
Attachment A BWR Approved Framatome Advanced Nuclear Power (FANP) Topical Reports for TS-425 COLR References Report Applicable LCO / Assembly Methodology / Justification Types XN-NF-81-58(P)(A) and Supplements 1 and 2, 3.2.1 / A1O Provides an analytical capability to predict BWR fhel thermal and mechanical I Revision 2 RODEX2 Fuel Rod Thermal-Mechanical 3.2.2 / AlO, GE13, GE14 conditions for normal core operation and to establish initial conditions for power Response EvaluationModel. 3.2.3 / A10 ramping, non-LOCA, and LOCA analyses. i i
XN-NF-85-67(P)(A) Revision 1, Generic 3.2.3 / A10 Describes the process used to develop linear heat generation rates for fnel designs.
MechanicalDesignfor Exxon NuclearJet Pump I BWR Reload Fuel.
EMP-85-74(P) Revision 0 Supplement l(P)(A) and 3.2.3 J AlO Extends the exposure limit ofthe RODEX2A code which is a version of RODEX2 1 Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod that includes a fission gas release model specific to BWR fuel designs.
Thermal-MechanicalEvaluationModels. i' r ANF-89-98(P)(A) Revision 1 and Supplement 1, 3.2.3 I A10 Establishes a set of design criteria which assures that BWR ffel will perfori Generic MechanicalDesign Citerafor B WR Fuel satisfactorily throughout its lifetime.
Designs.
XN-NF-80-19(P)(A) Volume I and Supplements 1 3.2.1 / A1O Development of BWR core analysis methodology which comprises codes for fuel and 2, Exxon NuclearMethodologyfor Boiling 3.2.2 / AlO, GE13, GE14 nentronic parameters and assembly brnup calculations, reactor core simulation Water ReactorsNeutronic Methodsfor Design and 3.2.3 / AlO diffnsion theory calculations, core and channd hydrodynamic stability predictions, Analysis. 3.3.2.1, Table 3.3.2.1-1 / and producing input for nuclear plant transients. Subsequently approved codes or A1O, GE13, GE14 methodologies have superceded portions ofthis reporL Applicable portions include CRDA, and methodology to determine nentronic reactivityparameters, void reactivity, Doppler reactivity, scram reactivity, delayed neutron fraction, and prompt neutron lifetime.
XN-NF-80-19(P)(A) Volume 4 Revision 1, Eaxon 3.2.1 / AlO Summarizes the types of BWR licensing analyses performed, identifies the NuclearMethodologyfor Boiling Water Reactors: 3.2.2 / AlO, GE13, GE14 methodologies used.
Application of the ENC Methodology to BWR 3.2.3 / AlO Reloads.
Attachment A 0
BWR Approved Framatome Advanced Nuclear Power (FANP) Topical Reports for TS-425 COLR References Report Applicable LCO / Assembly Methodology / Justification Types EM-2158(P)(A) Revision 0, Siemens Power 3.2.2 / AlO, GE13, GE14 Describes the reactor core simulator code MICROBURN-B2 and the lattice physics CorporationMethodologyfor Boiling Water 3.2.3 / AlO code CASMO-4.
Reactors: Evaluation and Validation of 3.3.2.1, Table 3.3.2. 1-1 /
CASMO-4/1MCROBURN-B2. AIO, GE13, GE14 XN-NF-80-19(PXA) Volume 3 Revision 2, Exxon 3.2.2/ AlO, GE13, GE14 Provides overall methodology for determining a MCPR operating limit.
NuclearMethodologyfor Boiling WaterReactors, ThERMEX: Thermal Limits Methodology Summary Description.
XN-NF-84-105(P)(A) Volume 1 and Volume 1 3.2.2 / Al1, GE13, GE14 Provides a capabilityto perform analyses oftransient heat transfer behavior in BWR Supplements I and 2, XCOBRA-T: A Computer Code assemblies.
for BWR Transient Thernal-HydraulicCore Analysis.
ANF-524(P)(A) Revision 2 Supplements 1 and 2, 3.2.2/ AlO, GE13, GE14 Provides a methodology for the determination of thermal margins, specifically the ANF CriticalPowerMethodologyfor Boiling Water MCPR safety limit Reactors.
ANF-913(P)(A) Volume 1 Revision I and Volume 1 3.2.2 I AlO, GE13, GE14 Provides a computer program for analyzing BWR system transients Supplements 2, 3 and 4, C0TRANSA2: A Computer ProgramforBoiling Water Reactor Transient Analyses.
ANF-1358(P)(A) Revision 1, The Loss of Feedwater 3.2.2 / AlO, GE13, GE14 Presents a generic methodology for evaluating the loss of feedwater heating event Heating Transient n Boiling Water Reactors.
Attachment A BWR Approved Framatome Advanced Nuclear Power (FANP) Topical Reports for TS-425 COLR References Report Applicable LCO / Assembly Methodology / Justification Types EMF-2209(P)(A) Revision 1, SPCB CriticalPower 3.2.2 / AIO, GE13, GE14 Presents an improved critical power corrdation for use with the ATRIUM-10 fnel Correlation. designs.
EMI-2245(P)(A) Revision 0, Application of Siemens 3.2.2 / GE13, GE14 Provides direct and indirect approaches to develop parameters necessary to Power Corporation'sCriffcal Power Correlationsto appropriately model co-resident fhel with an approved critical power correlation.
Co-Resident Fuel.
EMP-2361(P)(A) Revision 0, EXEMBWR -2000 3.2.1 / AlO Describes an upgraded evaluation model methodology for licensing analyses of ECCS EvaluationModel. postulated LOCAs in jet pump BWRs. The methodolOgy was developed to comply with 10 CFR 50.46 and Appendix K criteria to 10 CPR 50.
EMP-2292(P)(A) Revision 0, ATPJUAluw-0: 3.2.1 AlO Provides measured cladding temperatures from sprayheat transfer tests to justify the Appendix K Spray Heat TranerCoefficients. use of Appendix K coefficients for ATRIUM-10 fuel LOCA analyses.
Attachment B GESTAR-U COLR Limits for General Electric Fnel Applicable for a Transition Core with FANP Fuel TS-425 COLR References Applicable COLR GESTAR-I[ Applicability LCO / Assembly Types Specified Limit 3.2.1/ GE13, GE14 Average Planar Linear Heat Generation GESTAR-HI APLHGR limits documented in the BF3 Cycle 11 COLR remain applicable for GE13 Rate (APLHGR) and GE14 fd in the Cycle 12 transition core with FANP fuel.
The GESTAR-IH APLHGR limits are applied to off-rated power and flow conditions using ARTS factors MAPFAC, and MAPFACQ.
The GESTAR-il APLHGR limits are applied to the following Equipment Out-of-Service (EOOS) conditions-
- Turbine Bypass OOS (TS 3.7.5) 3.2.2 / Not Applicable Minimum Critical Power Ratio (MCPR) GESTAR-II will not be applied to establish MCPR operating limits.
OLMCPR for rated and off-rated power and flow conditions and EOOS operation will be established for GE13 and GE14 fel using FANP-approved methods identified in Attachment A.
3.2.3 / GED3, GE14 Linear Heat Generation Rate (LHGR) GESTAR-Il LHGR limits documented in the BF3 Cycle 11 COLR remain applicable fbr GE13 and GE14 fel in the Cyvle 12 transition core with FANP el.
No off-rated power or flow-dependent or EOOS corrections are applied to the LHGR limits for GE fed.
3.3.2.1 Table 3.3.2.1-1/ Rod Block Monitor (RBM) setpoints and GESTAR-Il will not be applied to establish RBM setpoints and applicable reactor thermal power Not Applicable applicable reactor thermal power ranges ranges.
The RBM setpoints and applicable thermal power ranges will be established using FANP approved methods identified in Attachment A.
Enclosure 2 Technical Specifications (TS) Change 425 Framatome Fuel - Core Operating Limits Report (COLR) References Units 2 and 3 Corrected-Pages (mark-up)
4 1 1 -.
EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:
- 1. Turbine Stop Valve (TSV) - Closure; and
- 2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure
- Low.=
OR
- b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"
limits for inoperable EOC-RPT as specified in the COLR are made applicable; Cwd APPLICABILITY: THERMAL POWER 2 30% RTP.
- c. LCO 3.2.3, LINEAR HEAT GENERATION RATE (LHGR),I limits for inoperable EOC-RPT as specified in the COLR are BFN-UNIT 2 3.3-30 Amendment No. 253
EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION :
3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:
- 1. Turbine Stop Valve (TSV) - Closure; and
- 2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure
- Low.
OR
- b. CO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR),"
limits for inoperable EOC-RPT as specified in the COLR are made applicable; en d &
THERMAL POWER 2 30% RTP.
BFN-UNIT 3 3.3-30 Amendment No. 213 September 03, 1998